The conceptual precepts of a modular fast sodium reactor with mixed uranium-plutonium zirconium-alloy metal fuel (U–Pu–Zr) related to Gen-IV are presented. The range of its parameters is determined, and the parameters are optimized in order to meet the characteristic requirements of the development of a nuclear power system in terms of safety, competitiveness, and resource availability. It was shown with the aid of computational studies that in a modular reactor, in spite of its small size, the systems requirements in terms of specific load and excess production are met and the minimum reactivity excess on burnup is realized. Loading metallic fuel into the core and thorium into the breeding zone and using fuel cycles compatible with thermal reactors it becomes much easier to solve the problems of supplying fuel for nuclear power and managing actinides and plutonium in the nuclear fuel cycle.
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References
Status of Small and Medium Sized Reactor Designs, a Supplement to the IAEA Advanced Reactors Information System (ARIS), IAEA, Vienna(2011).
V. M. Novikov, I. S. Slesarev, P. N. Alekseev, et al., Nuclear Reactors with Enhanced Safety (analysis of design concepts), Energoatomizdat, Moscow (1993).
P. N. Alekseev, V. G. Asmolov, A. Yu. Gagarinskii, et al., On a Strategy for Nuclear Power in Russia to 2050, Kurchatov Institute, Moscow (2012).
V. I. Matveev and Yu. S. Khomyakov, Technical Physics of Sodium-Cooled Fast Reactors, V. I. Pachkov (ed.), Izd. MEI, Moscow (2012).
Status and Trends of Nuclear Fuels Technology for Sodium Cooled Fast Reactors, IAEA Tech. Rep. Nucl. Energy Ser. No. NF-T-4.1, IAEA, Vienna (2011).
Yu. M. Golovchenko, Scientific and Technical Validation of Absorbing, Breeding, and Fuel Rods with Kernels Based on Metallic Uranium for BN-Type Fast Reactors: Doct. Dissert. in Techn. Sci., Dimitrovgrad (2002).
L. N. Yaroslavtseva, P. A. Fomichenko, and P. N. Alekseev, “Verification of stationary and nonstationary algorithms in the JAR complex,” in: Neutronics-92, Obninsk (1994), pp. 34–37.
P. N. Alekseev, E. A. Bobrov, A. V. Chibinyaev, et al., “Variants of the perspective closed fuel cycle, based on regenerated mixture – technology, combining use of thermal and fast reactors,” Progr. Nucl. Energy, 72, 126–129 (2014).
J. Lovering, A. Yip, and T. Nordhaus, “Historical construction costs of global nuclear power reactors,” Energy Policy, 91, 371–382 (2016).
V. Kuznetsov and N. Barkatullah, Approaches to Assess Competitiveness of Small and Medium Sized Reactors, IAEA, Vienna (2013).
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Translated from Atomnaya Énergiya, Vol. 126, No. 4, pp. 188–193, April, 2019.
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Kotov, Y.A., Alekseev, P.N. Basic Concepts of a Modular Fast Sodium Reactor with Metallic Fuel. At Energy 126, 213–219 (2019). https://doi.org/10.1007/s10512-019-00539-9
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DOI: https://doi.org/10.1007/s10512-019-00539-9